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Wilson, C.N.; Gray, W.J.
Pacific Northwest Lab., Richland, WA (USA)1989
Pacific Northwest Lab., Richland, WA (USA)1989
AbstractAbstract
[en] Dissolution rates were measured on crushed unirradiated UO2 fuel pellet samples under oxidizing conditions using a flow-through testing method. A thin U--Si--O surface alteration layer was identified by Auger microprobe examination of UO2 particles tested at 25 degree C in Ca--Si-containing waters, and a thin layer containing Ca + Si was identified on the surface of particles tested at 85 degree C. These experiments and their preliminary results are discussed as they apply to the potential disposal of spent nuclear fuel at the candidate Yucca Mountain repository site. 3 refs., 6 figs., 11 tabs
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Dec 1989; 6 p; International conference for high-level radioactive waste management; Las Vegas, NV (USA); 8-12 Apr 1990; CONF-900406--67; CONTRACT AC06-76RL01830; NTIS, PC A02/MF A01 as DE90009457; OSTI; INIS; US Govt. Printing Office Dep
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Conference
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ACTINIDE COMPOUNDS, ALKALINE EARTH METALS, CARBON COMPOUNDS, CHALCOGENIDES, ELEMENTS, ENERGY SOURCES, ENVIRONMENTAL TRANSPORT, FUELS, GEOLOGIC SURVEYS, HYDROGEN COMPOUNDS, MANAGEMENT, MASS TRANSFER, MATERIALS, METALS, MOUNTAINS, NUCLEAR FUELS, OXIDES, OXYGEN COMPOUNDS, POLAR SOLVENTS, REACTOR MATERIALS, SEMIMETALS, SOLVENTS, URANIUM COMPOUNDS, URANIUM OXIDES, WASTE DISPOSAL, WASTE MANAGEMENT
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